Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA

Detalhes bibliográficos
Autor(a) principal: GOMES, DANIEL S.
Data de Publicação: 2018
Outros Autores: TEIXEIRA, ANTONIO S., INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/28182
Resumo: Although regulatory agencies have shown a special interest in incorporating best estimate approaches in the fuel licensing process, fuel codes are currently licensed based on only the deterministic limits such as those seen in 10CRF50, and therefore, may yield unrealistic safety margins. The concept of uncertainty analysis is employed to more realistically manage this risk. In this study, uncertainties were classified into two categories: probabilistic and epistemic (owing to a lack of pre-existing knowledge in this area). Fuel rods have three sources of uncertainty: manufacturing tolerance, boundary conditions, and physical models. The first step in successfully analyzing the uncertainties involves performing a statistical analysis on the input parameters used throughout the fuel code. The response obtained from this analysis must show proportional index correlations because the uncertainties are globally propagated. The DAKOTA toolkit was used to analyze the FRAPTRAN transient fuel code. The subsequent sensitivity analyses helped in identifying the key parameters with the highest correlation indices including the peak cladding temperature and the time required for cladding failures. The uncertainty analysis was performed using an IFA-650-5 fuel rod, which was in line with the tests performed in the Halden Project in Norway. The main objectives of the Halden project included studying the ballooning and rupture processes. The results of this experiment demonstrate the accuracy and applicability of the physical models in evaluating the thermal conductivity, mechanical model, and fuel swelling formulations.
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spelling 2018-01-02T12:03:07Z2018-01-02T12:03:07ZOctober 22-27, 2017http://repositorio.ipen.br/handle/123456789/28182Although regulatory agencies have shown a special interest in incorporating best estimate approaches in the fuel licensing process, fuel codes are currently licensed based on only the deterministic limits such as those seen in 10CRF50, and therefore, may yield unrealistic safety margins. The concept of uncertainty analysis is employed to more realistically manage this risk. In this study, uncertainties were classified into two categories: probabilistic and epistemic (owing to a lack of pre-existing knowledge in this area). Fuel rods have three sources of uncertainty: manufacturing tolerance, boundary conditions, and physical models. The first step in successfully analyzing the uncertainties involves performing a statistical analysis on the input parameters used throughout the fuel code. The response obtained from this analysis must show proportional index correlations because the uncertainties are globally propagated. The DAKOTA toolkit was used to analyze the FRAPTRAN transient fuel code. The subsequent sensitivity analyses helped in identifying the key parameters with the highest correlation indices including the peak cladding temperature and the time required for cladding failures. The uncertainty analysis was performed using an IFA-650-5 fuel rod, which was in line with the tests performed in the Halden Project in Norway. The main objectives of the Halden project included studying the ballooning and rupture processes. The results of this experiment demonstrate the accuracy and applicability of the physical models in evaluating the thermal conductivity, mechanical model, and fuel swelling formulations.Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2018-01-02T12:03:07Z No. of bitstreams: 1 24007.pdf: 714918 bytes, checksum: c3f3aafa1f9a3c8be7a0f02c80dfd782 (MD5)Made available in DSpace on 2018-01-02T12:03:07Z (GMT). No. of bitstreams: 1 24007.pdf: 714918 bytes, checksum: c3f3aafa1f9a3c8be7a0f02c80dfd782 (MD5)Associa????o Brasileira de Energia Nuclearboundary conditionscomputerized simulationd codesdata covariancesf codesfuel rodsfuel-cladding interactionsnuclear fuelsprobabilistic estimationswellingthermal conductivitythermal expansiontransientsSimulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTAinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de Janeiro, RJBelo Horizonte, MGGOMES, DANIEL S.TEIXEIRA, ANTONIO S.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN240072017GOMES, DANIEL S.TEIXEIRA, ANTONIO S.18-01Proceedings76701085GOMES, DANIEL S.:7670:420:STEIXEIRA, ANTONIO S.:1085:420:NORIGINAL24007.pdf24007.pdfapplication/pdf714918http://repositorio.ipen.br/bitstream/123456789/28182/1/24007.pdfc3f3aafa1f9a3c8be7a0f02c80dfd782MD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/28182/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/281822022-08-05 19:08:32.967oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-08-05T19:08:32Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
title Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
spellingShingle Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
GOMES, DANIEL S.
boundary conditions
computerized simulation
d codes
data covariances
f codes
fuel rods
fuel-cladding interactions
nuclear fuels
probabilistic estimation
swelling
thermal conductivity
thermal expansion
transients
title_short Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
title_full Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
title_fullStr Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
title_full_unstemmed Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
title_sort Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
author GOMES, DANIEL S.
author_facet GOMES, DANIEL S.
TEIXEIRA, ANTONIO S.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 TEIXEIRA, ANTONIO S.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
dc.contributor.author.fl_str_mv GOMES, DANIEL S.
TEIXEIRA, ANTONIO S.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv boundary conditions
computerized simulation
d codes
data covariances
f codes
fuel rods
fuel-cladding interactions
nuclear fuels
probabilistic estimation
swelling
thermal conductivity
thermal expansion
transients
topic boundary conditions
computerized simulation
d codes
data covariances
f codes
fuel rods
fuel-cladding interactions
nuclear fuels
probabilistic estimation
swelling
thermal conductivity
thermal expansion
transients
description Although regulatory agencies have shown a special interest in incorporating best estimate approaches in the fuel licensing process, fuel codes are currently licensed based on only the deterministic limits such as those seen in 10CRF50, and therefore, may yield unrealistic safety margins. The concept of uncertainty analysis is employed to more realistically manage this risk. In this study, uncertainties were classified into two categories: probabilistic and epistemic (owing to a lack of pre-existing knowledge in this area). Fuel rods have three sources of uncertainty: manufacturing tolerance, boundary conditions, and physical models. The first step in successfully analyzing the uncertainties involves performing a statistical analysis on the input parameters used throughout the fuel code. The response obtained from this analysis must show proportional index correlations because the uncertainties are globally propagated. The DAKOTA toolkit was used to analyze the FRAPTRAN transient fuel code. The subsequent sensitivity analyses helped in identifying the key parameters with the highest correlation indices including the peak cladding temperature and the time required for cladding failures. The uncertainty analysis was performed using an IFA-650-5 fuel rod, which was in line with the tests performed in the Halden Project in Norway. The main objectives of the Halden project included studying the ballooning and rupture processes. The results of this experiment demonstrate the accuracy and applicability of the physical models in evaluating the thermal conductivity, mechanical model, and fuel swelling formulations.
publishDate 2018
dc.date.evento.pt_BR.fl_str_mv October 22-27, 2017
dc.date.accessioned.fl_str_mv 2018-01-02T12:03:07Z
dc.date.available.fl_str_mv 2018-01-02T12:03:07Z
dc.type.status.fl_str_mv info:eu-repo/semantics/publishedVersion
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dc.identifier.uri.fl_str_mv http://repositorio.ipen.br/handle/123456789/28182
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dc.publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
publisher.none.fl_str_mv Associa????o Brasileira de Energia Nuclear
dc.source.none.fl_str_mv reponame:Repositório Institucional do IPEN
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